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Investigation of non-magnetic alloys for the suppression of tritium permeation. Final report

Technical Report ·
DOI:https://doi.org/10.2172/5091758· OSTI ID:5091758
This report describes a small (300 man hour) literature survey relating to the suppression of tritium loss by permeation through the walls of fusion reactors. The program was based on prior in-house Thermacore work to suppress hydrogen permeation into high temperature (800/sup 0/C) heat pipes. The Thermacore approach involves selection of a steel with a small (.5 to 5%) aluminum content. The aluminum is diffused to the surface and oxidized. The present work was aimed at identification of alloys which might combine low tritium permeation with other properties desired in fusion reactor vessels, heat exchangers, lithium-handling plumbing and other components likely to contain tritium. These properties include low radiation damage, low magnetic permeability, high temperature strength, and compatibility with potential heat transfer and blanket materials. The work consisted of two tasks: Problem Definition and Literature Search and Analysis.
Research Organization:
Thermacore, Inc., Lancaster, PA (USA)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC05-79ER10087
OSTI ID:
5091758
Report Number(s):
DOE/ER/10087--T1
Country of Publication:
United States
Language:
English